Irradiation tests of radiation hard materials for ITER blanket remote handling system

Autor: Takahito Maruyama, Makiko Saito, Satoshi Kakudate, Hiroshi Kozaka, Nobukazu Takeda, Yuto Noguchi, Kentaro Nakata
Rok vydání: 2017
Předmět:
Zdroj: Fusion Engineering and Design. 124:542-547
ISSN: 0920-3796
DOI: 10.1016/j.fusengdes.2017.04.045
Popis: The ITER Blanket Remote Handling System (BRHS) will handle the blanket first walls (FWs) and shield blocks (SBs), which can weigh up to 4.5 ton and be larger than 1.5 m, stably and with a high degree of positioning accuracy. When the ITER has stopped plasma operations for maintenance, the BRHS will be installed in the vacuum vessel, whose components are radioactive, to remove and install the FWs and SBs. Therefore, the BRHS will be operated in a high radiation environment (up to 250 Gy/h) having an estimated total dose of 5 MGy during maintenance (maximum of two years). The radiation hardness requirement for ITER BRHS components is 1 MGy total dose. As components may degrade by gamma irradiation, some equipment is expected to malfunction which causes delays in the in-vessel maintenance schedule. Therefore, failure mode and effects analyses (FMEA) were performed on the BRHS components and FMEA results suggest trouble with the power supply and signals due to degradation of the insulation of electrical components, and malfunctioning motors due to degradation of the lubricants of mechanical components. In this study, material property tests for O-rings and coating materials were performed to verify radiation hardness after the irradiation with gamma rays up to 5 MGy.
Databáze: OpenAIRE